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Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code

机译:使用THALES子通道代码在低流量条件下进行反应堆堆芯分析

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During the operation of PWR (Pressurized Water Reactor) nuclear power plant, the minimum DNBR (Departure from Nucleate Boiling Ratio) should be maintained within the Tech. Spec. LCO (Limiting Conditions for Operation) to satisfy the acceptance criteria during AOO (Anticipated Operational Occurrence) and event condition. For the DNBR analysis, the calculation of the flow and energy fields is required. Some events may experience the low flow condition if the LOOP (Loss of Offsite Power) is occurred. The reactor core analysis at low flow condition is classified into two ways. One is for the power generation of the reactor core and the other is for DNBR calculation of hot node. Generally, the flow analysis for core power generation is more difficult. The representative event which experienced the low flow condition is SLB (Steam Line Break) event. During the SLB event with LOOP, the reactor core is tripped and all RCPs (Reactor Coolant Pump) are stopped. As a result, the flow rate and pressure in reactor core decrease and the peaking factor is relatively high compared to a nominal operating condition. For the prediction of state in the PWR reactor core, the reactor core analysis at low flow condition is performed using the subchannel code THALES (Thermal Hydraulic AnaLyzer for Enhanced Simulation of core) developed by KEPCO Nuclear Fuel. Since the subchannel analysis code was developed to solve the reactor core flow field at the high axial flow rate and pressure condition, the convergence at the low flow condition such as SLB is very difficult. Therefore, most of subchannel analysis codes fail to obtain the converged flow field at very low flow and high power, which has resulted to insufficient research of 3 dimensional analysis of SLB event. This paper will show why we have a trouble to obtain the converged result for the reactor core analysis at low flow condition. And we show the high distortion characteristics of the flow and energy fields at the low flow condition by using subchannel analysis code. Through the core flow analysis at low flow condition, it is verified that subchannel code THALES can predict reasonable results despite of the extreme condition and that the distortion of the flow and energy field is huge.
机译:在压水堆(压水堆)核电站运行期间,应在技术范围内保持最小DNBR(偏离核沸腾比)。规格LCO(操作的限制条件)满足AOO(预期的操作发生)和事件条件期间的接受标准。对于DNBR分析,需要计算流场和能量场。如果发生LOOP(非现场功率损失),则某些事件可能会遇到流量低的情况。低流量条件下的反应堆堆芯分析分为两种方法。一种用于反应堆堆芯的发电,另一种用于热节点的DNBR计算。通常,用于核心发电的流量分析更加困难。经历低流量条件的代表事件是SLB(蒸汽管线中断)事件。在带有LOOP的SLB事件期间,反应堆堆芯跳闸并且所有RCP(反应堆冷却剂泵)都停止了。结果,与标称运行条件相比,反应堆堆芯中的流速和压力降低,并且峰值因数相对较高。为了预测PWR反应堆堆芯的状态,使用KEPCO核燃料公司开发的子通道代码THALES(用于堆芯增强的热力水力分析仪)进行低流量条件下的反应堆堆芯分析。由于开发了子通道分析代码来解决高轴向流量和压力条件下的反应堆堆芯流场,因此在低流量条件下(例如SLB)的收敛非常困难。因此,大多数子信道分析代码无法在非常低的流量和较高的功率下获得收敛的流场,这导致对SLB事件的三维分析的研究不足。本文将说明为什么我们在低流量条件下难以获得反应堆堆芯分析的收敛结果。并通过子通道分析代码展示了低流量条件下流场和能量场的高畸变特性。通过在低流量条件下的岩心流动分析,验证了即使在极端条件下,子信道代码THALES仍可以预测合理的结果,并且流场和能量场的失真很大。

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